Thermal Analysis of the Pennsylvania State University Breazeale Nuclear Reactor-Reference-Cited by-同舟云学术

Thermal Analysis of the Pennsylvania State University Breazeale Nuclear Reactor

Published:1973-07 Issue:1 Volume:19 Page:6-15
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Haag J. A.¹,Levine S. H.²

Affiliation:

1. Knolls Atomic Laboratory, Schenectady, New York 12301

2. The Breazeale Nuclear Reactor The Pennsylvania State University University Park, Pennsylvania 16802

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT73-A31313

Reference8 articles.

1. D. A. ROSS, “The Pennsylvania State University TRIGA Reactor—Description, Initial Testing, and First Three Years of Operation,” MS Thesis, The Pennsylvania State University (June 1969).

2. R. F. BARRY, “LEOPARD,” WCAP-3296-26, Westinghouse Electric Corp. (1963).

3. T. B. FOWLER, M. L. TOBIAS.S, and D. R. VONDY, “EXTERMINATOR II-A FORTRAN II Code for Solving Multigroup Neutron Diffusion Equations in Two Dimensions,” ORNL-4078, Oak Ridge National Laboratory (1967).

4. W. A. GOODWIN, “The Measurement of Radial Power Distribution in a TRIGA Fuel Element,” PhD Thesis (1968).

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